Production and Testing of the VITAMIN-B7 Fine-Group and BUGLE-B7 Broad-Group Coupled Neutron/Gamma Cross-Section Libraries Derived from ENDF/B-VII.0 Nuclear Data (NUREG/CR-7045, ORNL/TM 2011/12)) Technical Report January, 2011
Sensitivity and Uncertainty Analysis of Commercial Reactor Criticals for Burnup Credit (NUREG/CR-6951, ORNL/TM-2006/87) Technical Report January, 2007